US4363777A - Closure element for limiting the convection currents in an annular space about a nuclear reactor component - Google Patents

Closure element for limiting the convection currents in an annular space about a nuclear reactor component Download PDF

Info

Publication number
US4363777A
US4363777A US06/203,764 US20376480A US4363777A US 4363777 A US4363777 A US 4363777A US 20376480 A US20376480 A US 20376480A US 4363777 A US4363777 A US 4363777A
Authority
US
United States
Prior art keywords
component
cup
annular space
closure
sleeve
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired - Lifetime
Application number
US06/203,764
Inventor
Bernard Cornu
Jean-Louis Pierrey
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Novatome SA
Original Assignee
Novatome SA
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Novatome SA filed Critical Novatome SA
Assigned to NOVATOME, reassignment NOVATOME, ASSIGNMENT OF ASSIGNORS INTEREST. Assignors: CORNU BERNARD, PIERREY JEAN-LOUIS
Application granted granted Critical
Publication of US4363777A publication Critical patent/US4363777A/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

Links

Images

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/02—Details
    • G21C13/028—Seals, e.g. for pressure vessels or containment vessels
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10S277/00—Seal for a joint or juncture
    • Y10S277/921—Closure or weather strip seal

Definitions

  • the invention concerns a closure apparatus for limiting the convection currents in an annular space about a component of a fast neutron nuclear reactor cooled by a liquid metal having a vessel closed by a very thick horizontal plate in which vertical cylindrical passages are made for the passage of removable components vertically disposed in the reactor and resting on the plate.
  • Such components are components with very large dimensions such as the primary pump, the intermediate exchanger or the coolant fluid preheating pipe or components of smaller dimensions such as the apparatus incorporated for purification of the coolant fluid.
  • the components enter vertically into the vessel of the reactor containing the liquid metal, generally liquid sodium, at passages made in the reactor plate.
  • passages are provided with a diameter sufficiently larger than the diameter of the component for there to be an annular space of relatively great width between the outer surface of the component where this component passes through the plate and the inner surface of the passage constituted by a cylindrical sleeve fixed in an aperture in the plate.
  • Sealing between the component and the reactor vessel, when the component is in position, is achieved by seals at the upper enlarged part of the component resting on the plate.
  • An annular cup has therefore been designed, disposed on the inner surface of the sleeve constituting the passage in the plate and in particular its periphery, inside which a sleeve solid with the outer surface of the component is positioned, when the component is put into position for use in the reactor.
  • the annular cup fills with liquid sodium from the vapor condensed in this hollow receptacle disposed in a region which is cooler than the inner space of the vessel.
  • the sleeve solid with the component dips into a liquid metal which creates a barrier against convection currents and flows of sodium vapor.
  • the object of the invention is therefore to propose a closure apparatus for limiting the convection currents in an annular space about a component of a fast neutron nuclear reactor cooled by a liquid metal, having a vessel closed by a very thick horizontal plate in which vertical cylindrical passages are provided for the passage of removable components disposed vertically in the reactor and resting on the plate, each of these components having between its outer surface and the inner surface of the corresponding passage an annular space of a certain width in which is positioned the closure apparatus of the type with an annular cup solid with the component and surrounding its outer wall and containing a liquid into which a sleeve dips so as to ensure closure of the annular space about the component, this apparatus being intended to allow limitation of the convection currents and the flows of sodium inside the annular passage while avoiding complicating the handling manerises involved in putting the component in position or removing it.
  • the apparatus also has:
  • a frusto-conical support surface having as axis the vertical axis common to the component and the passage, fixed at the perimeter of its large base to the passage, and having its small base disposed at a level lower than the level of the large base, with a diameter greater than the external diameter of the cup,
  • the single FIGURE represents a sectional half-view of the part of a component disposed at a passage of the vessel of a fast neutron reactor and of the closure apparatus according to the invention.
  • the FIGURE shows the component 1, substantially cylindrical in shape, disposed inside a cylindrical space provided in the plate 3 of a fast neutron nuclear reactor.
  • the cylindrical aperture of the plate bounded by a cylindrical sleeve 4 and the component 1 have the vertical axis 2 as common axis of symmetry when the component is in position as represented in the single FIGURE.
  • annular cup 5 On the outer surface of the component and completely surrounding this component, an annular cup 5 is disposed, whose vertical, inwardly disposed wall 6 is welded to the body of the component.
  • a frusto-conical support element 9 is welded at the perimeter of its upwardly disposed large base.
  • the axis of the frusto-conical element 9 coincides with the axis 2 common to the passage and the component.
  • This element 9 is held rigid by a set of supporting brackets such as 10 fixed on the sleeve 4.
  • the diameter of the downwardly disposed small base of this frusto-conical element is greater than the external diameter of the cup, i.e. than the diameter of the sleeve 12 constituting the outer wall of the cup.
  • the closure element 14 completing the apparatus is constituted by a toroidal ring 15 resting on the upper surface of the frusto-conical element 9 constituting the support surface and a sleeve 16 welded to this toridal ring, so that the whole of the closure element 14 presents a rotational symmetry with respect to the axis 2.
  • the lower part of the annular space is thus isolated from the upper part of this space above the closure apparatus since the ring 15 rests on the upper surface of the frusto-conical element 9 and ensures a degree of sealing which allows too intense a circulation of convection currents and of sodium vapor from the lower part to the upper part of the annular space 18, into which argon is sent to ensure sealing, to be avoided.
  • the closure apparatus 14 comes to rest with the lower part of the sleeve 16 on the bottom of the cup 5. The whole of the apparatus 14 is then raised above the frusto-conical support element 9.
  • closure apparatus is very efficient, positions itself correctly and automatically when the component is handled, is very easily installed and also allows problems relating to expansion and movement of the component with respect to the passage to be avoided.
  • the cup can be any shape, since its section in a meridian plane shown in the single FIGURE does not have to be square or rectangular.
  • the closure apparatus 14 with rotational symmetry about the axis 2 can also differ in shape from the one represented in the FIGURE and in particular the sleeve 16 can have a frusto-conical part joining with a cylindrical part.
  • the upper part of the cup can also have a surface for supporting or guiding the closure apparatus when the component is put in position.
  • the apparatus according to the invention is applicable in all nuclear reactors cooled by a liquid metal.

Abstract

The apparatus comprises an annular cup (5) solid with the component (1) and surrounding its outer wall, a frusto-conical support surface (9) having as axis the vertical axis (2) of the component (1) fixed at the perimeter of its large base to the passage (4) into which the component (1) passes and a closure element (14) with rotational symmetry. The closure element (14) has an upper part (15) which rests on the support surface (9) so as to totally close the annular space (18) at the top and a part directed downwards constituted by a sleeve whose lower part goes into the cup (5). The cup (5) fills up with liquid metal (17) which condenses when the reactor is operating, which ensures sealing between the sleeve (4) and the cup (5).
The invention is particularly applicable to fast neutron nuclear reactors cooled by liquid sodium.

Description

FIELD OF THE INVENTION
The invention concerns a closure apparatus for limiting the convection currents in an annular space about a component of a fast neutron nuclear reactor cooled by a liquid metal having a vessel closed by a very thick horizontal plate in which vertical cylindrical passages are made for the passage of removable components vertically disposed in the reactor and resting on the plate.
Examples of such components are components with very large dimensions such as the primary pump, the intermediate exchanger or the coolant fluid preheating pipe or components of smaller dimensions such as the apparatus incorporated for purification of the coolant fluid.
These components must be removable in all instances so as to allow their replacement or repair after the reactor has been operating for a certain time.
The components enter vertically into the vessel of the reactor containing the liquid metal, generally liquid sodium, at passages made in the reactor plate.
To facilitate handling of the elements, passages are provided with a diameter sufficiently larger than the diameter of the component for there to be an annular space of relatively great width between the outer surface of the component where this component passes through the plate and the inner surface of the passage constituted by a cylindrical sleeve fixed in an aperture in the plate.
Sealing between the component and the reactor vessel, when the component is in position, is achieved by seals at the upper enlarged part of the component resting on the plate.
It is therefore necessary to limit the convection currents between the interior of the vessel containing liquid sodium and the upper part of the component resting on the plate, inside the annular space between component and passage, in order to avoid inadmissable heating of the support structure. It is also essential to limit as much as possible the circulation of sodium vapor to the upper level of the component so as to avoid jamming of this component at extraction thereof.
PRIOR ART
An annular cup has therefore been designed, disposed on the inner surface of the sleeve constituting the passage in the plate and in particular its periphery, inside which a sleeve solid with the outer surface of the component is positioned, when the component is put into position for use in the reactor.
When the reactor is started up again, the annular cup fills with liquid sodium from the vapor condensed in this hollow receptacle disposed in a region which is cooler than the inner space of the vessel.
In this way, the sleeve solid with the component dips into a liquid metal which creates a barrier against convection currents and flows of sodium vapor.
However, when the component is put in position, positioning of the sleeve solid with the component inside the annular cup is a tricky operation during which deformation or destruction of the sleeve and the annular socket can occur. The same is true if the cup is solid with the outer surface of the component and the sleeve with the passage in the plate.
SUMMARY OF THE INVENTION
The object of the invention is therefore to propose a closure apparatus for limiting the convection currents in an annular space about a component of a fast neutron nuclear reactor cooled by a liquid metal, having a vessel closed by a very thick horizontal plate in which vertical cylindrical passages are provided for the passage of removable components disposed vertically in the reactor and resting on the plate, each of these components having between its outer surface and the inner surface of the corresponding passage an annular space of a certain width in which is positioned the closure apparatus of the type with an annular cup solid with the component and surrounding its outer wall and containing a liquid into which a sleeve dips so as to ensure closure of the annular space about the component, this apparatus being intended to allow limitation of the convection currents and the flows of sodium inside the annular passage while avoiding complicating the handling maneuvres involved in putting the component in position or removing it.
With this object, the apparatus also has:
a frusto-conical support surface having as axis the vertical axis common to the component and the passage, fixed at the perimeter of its large base to the passage, and having its small base disposed at a level lower than the level of the large base, with a diameter greater than the external diameter of the cup,
and a closure element with rotational symmetry not connected to the cup and the support surface having an upper part intended to rest on the support surface so as to totally close the annular space at the top when the component is put in position in the reactor, the cup being then below the support surface, and a part directed downwards constituted by the sleeve resting in the cup when the component is handled and ensuring closure of the annular space at the bottom, when the reactor is in service, the cup then filling up with liquid metal.
BRIEF DESCRIPTION OF THE DRAWING
To enable the invention to be fully understood, an embodiment of the apparatus according to the invention will now be described by way of non-limiting example, with reference to the single attached FIGURE.
The single FIGURE represents a sectional half-view of the part of a component disposed at a passage of the vessel of a fast neutron reactor and of the closure apparatus according to the invention.
DETAILED DESCRIPTION OF AN EMBODIMENT
The FIGURE shows the component 1, substantially cylindrical in shape, disposed inside a cylindrical space provided in the plate 3 of a fast neutron nuclear reactor.
The cylindrical aperture of the plate bounded by a cylindrical sleeve 4 and the component 1 have the vertical axis 2 as common axis of symmetry when the component is in position as represented in the single FIGURE.
On the outer surface of the component and completely surrounding this component, an annular cup 5 is disposed, whose vertical, inwardly disposed wall 6 is welded to the body of the component.
On the inner surface of the sleeve 4 facing towards the component, a frusto-conical support element 9 is welded at the perimeter of its upwardly disposed large base.
The axis of the frusto-conical element 9 coincides with the axis 2 common to the passage and the component.
This element 9 is held rigid by a set of supporting brackets such as 10 fixed on the sleeve 4.
The diameter of the downwardly disposed small base of this frusto-conical element is greater than the external diameter of the cup, i.e. than the diameter of the sleeve 12 constituting the outer wall of the cup.
The closure element 14 completing the apparatus is constituted by a toroidal ring 15 resting on the upper surface of the frusto-conical element 9 constituting the support surface and a sleeve 16 welded to this toridal ring, so that the whole of the closure element 14 presents a rotational symmetry with respect to the axis 2.
In the single FIGURE, the elements constituting the closure apparatus are shown in the position in which this closure is obtained, with the nuclear reactor in operation.
Sodium vapor then rises up from the part of the vessel containing liquid sodium to the annular space and condenses in the cup 5, constituting a seal of liquid metal 17 into which the lower part of the sleeve 16 dips.
The lower part of the annular space is thus isolated from the upper part of this space above the closure apparatus since the ring 15 rests on the upper surface of the frusto-conical element 9 and ensures a degree of sealing which allows too intense a circulation of convection currents and of sodium vapor from the lower part to the upper part of the annular space 18, into which argon is sent to ensure sealing, to be avoided.
When the component 1 is being removed and this component is raised in the direction along the axis 2, the closure apparatus 14 comes to rest with the lower part of the sleeve 16 on the bottom of the cup 5. The whole of the apparatus 14 is then raised above the frusto-conical support element 9.
No special precautions have to be taken when the component 1 is put back in position, since, when the component is lowered into its service position, the apparatus 14 moves into position on the support element 9 and centres automatically through the toroidal ring and the frusto-conical support surface.
When the power of the reactor increases, following its starting up, sodium vapor rises to the level of the cup 5 and fills this cup up again so as to constitute a seal of liquid metal 17.
The principal advantages of the invention, as shown, are therefore that the closure apparatus is very efficient, positions itself correctly and automatically when the component is handled, is very easily installed and also allows problems relating to expansion and movement of the component with respect to the passage to be avoided.
However, the invention is not limited to the embodiment just described; it also includes all the variants thereof.
Thus, the cup can be any shape, since its section in a meridian plane shown in the single FIGURE does not have to be square or rectangular.
The closure apparatus 14 with rotational symmetry about the axis 2 can also differ in shape from the one represented in the FIGURE and in particular the sleeve 16 can have a frusto-conical part joining with a cylindrical part.
The upper part of the cup can also have a surface for supporting or guiding the closure apparatus when the component is put in position.
Lastly, the apparatus according to the invention is applicable in all nuclear reactors cooled by a liquid metal.

Claims (2)

We claim:
1. Closure apparatus to limit convection currents in an annular space (18) about a component (1) of a nuclear reactor cooled by a liquid metal, having a vessel closed by a very thick horizontal plate in which vertical cylindrical passages are provided for the passage of removable components disposed vertically in the reactor and resting on the plate, each of the components having between its outer surface and the inner surface of the passage an annular space (18) of a certain width in which is positioned the closure apparatus of the type having an annular cup (5) solid with the component (1) and surrounding its outer wall and containing a liquid into which a sleeve (16) dips so as to ensure closure of the annular space (18) about the component (1) characterised by the fact that it also has:
a frusto-conical support surface (9) having as axis the vertical axis common to the component and the passage fixed at the perimeter of its large base at the passage and having its small base disposed at a lower level than the level of the large base, of a diameter greater than the external diameter of the cup (5),
and a closure element (14) with rotational symmetry, not connected to the cup (5) and the support surface (9), having an upper part (15) intended to come to rest on the support surface (9) so as to totally close the annular space (18) at the top when the component is put in position in the reactor, the cup (5) being then below the support surface (9) and a part directed downwards constituted by the sleeve (16) resting in the cup (5) when the component (1) is handled and ensuring closure of the annular space (18) at the bottom, when the reactor is in service, the cup (5) then filling up with liquid metal.
2. Closure apparatus according to claim 1, characterised by the fact that the sleeve (16) constituting the lower part of the closure element (14) has a cylindrical part and a frusto-conical part.
US06/203,764 1979-11-23 1980-11-03 Closure element for limiting the convection currents in an annular space about a nuclear reactor component Expired - Lifetime US4363777A (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR7928879A FR2470433A1 (en) 1979-11-23 1979-11-23 CLOSURE DEVICE FOR LIMITING CONVECTION CURRENTS IN ANNULAR SPACE AROUND A COMPONENT OF A NUCLEAR REACTOR
FR7928879 1979-11-23

Publications (1)

Publication Number Publication Date
US4363777A true US4363777A (en) 1982-12-14

Family

ID=9232012

Family Applications (1)

Application Number Title Priority Date Filing Date
US06/203,764 Expired - Lifetime US4363777A (en) 1979-11-23 1980-11-03 Closure element for limiting the convection currents in an annular space about a nuclear reactor component

Country Status (4)

Country Link
US (1) US4363777A (en)
EP (1) EP0029781B1 (en)
DE (1) DE3061924D1 (en)
FR (1) FR2470433A1 (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4495137A (en) * 1981-01-21 1985-01-22 Doryokuro Kakunenryo Kaihatsu Jigyodan Nuclear reactor
US4634569A (en) * 1981-11-16 1987-01-06 Jeumont-Schneider Corporation Device permitting reduction of thermosiphon effects in fast neutron nuclear reactors
US5911628A (en) * 1996-03-28 1999-06-15 Fichtel & Sachs Ag Flywheel device with a seal for a grease chamber

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4746485A (en) * 1986-11-19 1988-05-24 The United States Of America As Represented By The United States Department Of Energy Rotating shielded crane system
FR2989505B1 (en) * 2012-04-11 2014-04-25 Didier Costes NUCLEAR REACTOR WITH SINGLE COOLED TANK

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE931598C (en) * 1953-04-21 1955-08-11 Telefunken Gmbh Relay chain circuit with latching relay
US3324007A (en) * 1964-10-02 1967-06-06 English Electric Co Ltd Fluid seal and nuclear reactor system including same
US3877488A (en) * 1973-01-02 1975-04-15 Dorr Oliver Inc Venturi scrubber expansion joint

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB878940A (en) * 1957-06-24 1961-10-04 Atomic Energy Authority Uk Improvements in or relating to support means for nuclear reactors
US2991905A (en) * 1959-12-30 1961-07-11 Monson Harry Gas seal
FR1295407A (en) * 1961-04-14 1962-06-08 Commissariat Energie Atomique Improvements to the processes for making an alloy adhere to a metal surface and to the assemblies obtained by these processes
FR2045605A1 (en) * 1969-06-06 1971-03-05 Commissariat Energie Atomique Seal for a rotary cap of a reactor vessel
DE2327911A1 (en) * 1973-06-01 1974-12-19 Licentia Gmbh STATIONARY FLOOD COMPENSATOR FOR NUCLEAR REACTORS
FR2269774B1 (en) * 1974-05-02 1978-01-20 Commissariat Energie Atomique

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE931598C (en) * 1953-04-21 1955-08-11 Telefunken Gmbh Relay chain circuit with latching relay
US3324007A (en) * 1964-10-02 1967-06-06 English Electric Co Ltd Fluid seal and nuclear reactor system including same
US3877488A (en) * 1973-01-02 1975-04-15 Dorr Oliver Inc Venturi scrubber expansion joint

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4495137A (en) * 1981-01-21 1985-01-22 Doryokuro Kakunenryo Kaihatsu Jigyodan Nuclear reactor
US4634569A (en) * 1981-11-16 1987-01-06 Jeumont-Schneider Corporation Device permitting reduction of thermosiphon effects in fast neutron nuclear reactors
US5911628A (en) * 1996-03-28 1999-06-15 Fichtel & Sachs Ag Flywheel device with a seal for a grease chamber

Also Published As

Publication number Publication date
EP0029781A1 (en) 1981-06-03
EP0029781B1 (en) 1983-02-09
FR2470433B1 (en) 1983-12-23
DE3061924D1 (en) 1983-03-17
FR2470433A1 (en) 1981-05-29

Similar Documents

Publication Publication Date Title
US4498011A (en) Device for receiving, moving and radiation-shielding of vessels filled with expended reactor fuel elements
US4610838A (en) Method for removing debris from a nuclear reactor vessel
US4363777A (en) Closure element for limiting the convection currents in an annular space about a nuclear reactor component
JPH04213098A (en) Fuel-assembly moving basket for pool type reactor
US11538599B2 (en) Nuclear reactor provided with a raised heat exchanger
JPH0395489A (en) Liquid metal cooling type nclear reactor with passive cooling system
US5325407A (en) Core barrel and support plate assembly for pressurized water nuclear reactor
US4842815A (en) Device for locking a guide ring on a plate having an orifice and its use for a guide tube of a nuclear reactor
GB2139407A (en) Device for closing a storage container for radioactive materials
JPH0743436B2 (en) Self-aligning closure for maintenance service of reactor pressure vessels
US3995918A (en) System for bearing a nuclear reactor vessel cooled by liquid metal
US4671922A (en) Nuclear reactor cooled by a liquid metal
US3801448A (en) Removable top shield for a nuclear reactor core
US2826624A (en) Vapor shield for induction furnace
US4492667A (en) Fast neutron nuclear reactor
CN116057640A (en) Cassette core barrel for nuclear reactor
US3848423A (en) Handling system for nuclear fuel assemblies
US5410565A (en) Furnace, in particular an electric furnace, for treating liquid metal
US5013521A (en) Internal shell of a fast-neutron nuclear reactor comprising a thermal protection device
JPS6145990A (en) Gas-cooling high-temperature nuclear reactor
US4634569A (en) Device permitting reduction of thermosiphon effects in fast neutron nuclear reactors
JPH03257398A (en) Tank type fast breeder reactor
JPS63115094A (en) Cooling device for main vessel of liquid metal cooling type fast neutron reactor
US4560530A (en) Device for providing protection against heat and radiation for an intermediate heat exchanger immersed in a nuclear reactor vessel
JPH0533360B2 (en)

Legal Events

Date Code Title Description
AS Assignment

Owner name: NOVATOME, 20 AVENUE EDOUARD HERRIOT, 92350 LE PLES

Free format text: ASSIGNMENT OF ASSIGNORS INTEREST.;ASSIGNORS:CORNU BERNARD;PIERREY JEAN-LOUIS;REEL/FRAME:003827/0862

Effective date: 19810203

STCF Information on status: patent grant

Free format text: PATENTED CASE